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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K9681999-10-19019 October 1999 Ack Receipt of Transmitting Rev 40 to Physical Security Plan for Washington Nuclear Plant 2.Based on Determination That Changes Do Not Decrease Effectiveness of Plan,No NRC Approval Required ML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML20206U4501999-05-19019 May 1999 Ack Receipt of Which Transmitted Rev 39 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required,Since Changes Do Not Decrease Effectiveness of Security Plan ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule ML20196K6961999-03-30030 March 1999 Ack Receipt of ,Transmitting Rev 38 to Physical Security Plan for Plant.No NRC Approval Is Required,In Accordance with 10CFR50.54(p) GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML20204F0261999-03-19019 March 1999 Forwards Insp Rept 50-397/99-01 on 990201-04 & 0303-05.No Violations Noted.Areas of Physical Security Plan Effectively Implemented with Listed Exceptions ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17284A8981999-10-14014 October 1999 Forwards Rev 0 to WNP-2 Cycle 15,COLR 99-15, IAW Requirements of TS 5.6.5 ML17284A9061999-09-24024 September 1999 Forwards Final Rept for 990812 out-of-sequence Drills for Energy Northwest Washington Nuclear Power Project 2 (Lab, Food Control Point & Milk Sampling).No Deficiences & No Areas Requiring C/A Identified in Three Drills ML17292B7591999-09-24024 September 1999 Forwards Rev 24 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b), 50.54(q) & 10CFR50 App E.Detailed Synopsis of Changes,Encl ML17284A8881999-09-24024 September 1999 Informs NRC of Change in Schedule Pertaining to Final Implementation of Reactor Stability long-term Solution for WNP-2 ML17292B7581999-09-22022 September 1999 Forwards NRC Forms 396 & 398 for Nl Hancock,License SOP-50027-3,AR Herrington,License OP-50013-3,WH Sawyer, License SOP-50023-3 & Dl Strote,License SOP-50031-3,for Renewal of Licenses.Without NRC Forms 396 & 398 ML17284A8811999-09-0909 September 1999 Forwards Response to NRC 990623 RAI to Support Review of Pending Request for Amend to Reactor pressure-temp Limit Curve TS GO2-99-168, Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3)1999-09-0808 September 1999 Forwards Rev 40 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(a)(3) ML17284A8751999-08-30030 August 1999 Provides Correct Page from License NPF-21 Marked to Show Rev Addressed in 990729 Application for Amend,Which Included Page That Was Inadvertently Included as Attachment 4.Replace Attachment 4 with Attached Page & Disregard Attachment 5 ML17284A8721999-08-30030 August 1999 Forwards Proprietary Info to Support Review of Request for Amend to License NPF-21,re Min Critical Power Ratio Safety Limits Tss,As Requested During 990816 Conversation. Proprietary Encl Withheld ML17284A8711999-08-30030 August 1999 Informs Staff of Errors in world-wide-web Database Related to WNP-2 Reactor Vessel Structural integrity.Marked-up Pages Containing Errors or Omissions Will Be Forwarded by 991201 ML17292B7531999-08-24024 August 1999 Requests That Eleven Individuals Listed Below Take BWR Generic Fundamentals Examination to Be Administered on 991006 ML17292B7511999-08-24024 August 1999 Forwards Fitness for Duty (FFD) Semiannual Performance Data Rept for Jan-June 1999,per 10CFR26.71(d) ML17284A8701999-08-19019 August 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee & NRC Form 398, Personal Qualification Statement - Licensee, for Jd Prescott (License SOP-50262-1).Without Encls ML17292B7501999-08-19019 August 1999 Informs Staff That Licensee Has Completed Review of NRC SER for B&Wog Util Resolution Guidance Document Addressing ECCS Suction Strainer Blockage ML17284A8681999-08-12012 August 1999 Submits Two ISI Program Plan Relief Requests for NRC Review & Approval,Per 10CFR50.55a(a)(3)(i).Proposed Alternatives Provide Acceptable Level of Quality & Safety ML17284A8541999-08-0202 August 1999 Forwards Proprietary Addl Info to Support Review of Pending Request for Amend to MCPR Safety Limit Ts.Info Consists of Proprietary Ltr from Abb Combustion Engineering,Inc.Encl Withheld ML17284A8531999-07-30030 July 1999 Forwards Estimate of Number of Licensing Action Requests Planned for Submittal in Future,As Requested in Administrative Ltr 99-02.Twenty-nine Submittals Scheduled for Fy 2000 & Four for Fy 2001 ML17284A8301999-07-22022 July 1999 Clarifies Change of Licensee Name from Wpps to Energy Northwest & Change of Facility Name from Wppss Nuclear Project Number 2 to WNP-2,as Requested in 990719 Telcon with Js Cushing of NRC.Marked-up OL Pages,Encl ML17292B7451999-07-20020 July 1999 Forwards Rev 23 to WNP-2 Emergency Plan,Iaw 10CFR50.4(b) & 50.54(q) & 10CFR50 App E.Rev 23 Provides Updated Description Re Establishment of Separate Emergency Operation Centers for Benton & Franklin Counties ML17292B7391999-07-16016 July 1999 Submits Withdrawal of Request for Amend to Secondary Containment & Standby Gas Treatment Sys Ts.Util Currently Plan to re-submit Amend Request in Entirety by 991112 ML17292B7381999-07-12012 July 1999 Forwards NRC Form 396 & NRC Form 398,for If Sumsion,License OP-50487 & Ga Westergard,License SOP-50415 for Renewal of Operator Licenses.Without Encls ML17292B7171999-07-0606 July 1999 Provides Notification of Early Completion on 990630 of Exception Noted in 990629 Ltr.Equipment within Scope of GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants, Evaluated & Y2K Ready ML17292B7181999-07-0202 July 1999 Responds to 990623 RAI to Support Review of Evaluation of Planar Indication Found on Weld Number 24RRC(2)A-1 During 1998 RO ML17292B7161999-06-30030 June 1999 Forwards Addl Info Requested in 990513 Ltr to Support Review of Pending Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves. ML17292B7131999-06-29029 June 1999 Forwards Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. ML17292B7091999-06-21021 June 1999 Forwards Proprietary Response to NRC 990603 RAI Re Licensee Request for Amend to MCPR Safety Limit Tss.Proprietary Info Withheld IAW Requirements of 10CFR2.790 ML17292B7041999-06-17017 June 1999 Forwards NRC Forms 396 & 398 for Three Individuals Listed Below for Renewal of Operator Licenses.Without Encls ML17292B7031999-06-10010 June 1999 Forwards Response to NRC 990511 RAI Re License Request for Amend to Secondary Containment & SGTS Tss.Results of Addl Benchmark of Gothic Computer Code Performed to Demonstrate Modeling Capability of Drawdown Response,Encl ML17292B6841999-06-0404 June 1999 Forwards Response to NRC 990326 RAI Re WNP-2 GL 96-05 Program for Periodic Verification of design-basis Capability of MOVs ML17292B6851999-06-0101 June 1999 Forwards 1999 Quality Audit of WNP-2 Emergency Preparedness Program, Per NUREG-0654,Section Ii,Criteria P.9.Seven Problem Evaluation Requests & Nine Recommendations for Improvement Were Issued as Result of Audit Activities ML17292B6751999-05-25025 May 1999 Forwards Proprietary ABB-CE Ltr Re WNP-2 Cycle 15 SLMCPR & Core Reload Design Rept,Per Util Request for Amend Re MCPR Safety Limits.Proprietary Info Withheld,Per 10CFR2.790 ML17292B6831999-05-25025 May 1999 Informs That Request for NRC Approval of Changes to Emergency Plan Requesting Reduction in on-shift HP Staffing, Is Retracted.Util Will Resubmit Request with Required Addl Info at Later Date ML17292B6661999-05-0707 May 1999 Requests Exemption to Requirement in 10CFR55.59(a)(2) Re Annual Operating Test requirements.One-time Exemption from Requirement to Period Not to Exceed 15-months from Last Date of Passing Operating Exam for Licensee at Facility ML17292B6531999-05-0303 May 1999 Forwards Response to NRC 990402 RAI Re Licensed Operator Positive Drug Test.Encl Withheld,Per 10CFR2.790 ML17292B6561999-04-29029 April 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam ML17292B6421999-04-19019 April 1999 Responds to NRC 990319 Ltr Re Violations Noted in Insp Rept 50-397/99-01.Corrective Actions:Provisions Are Presently in Place to Maintain Adequate Level of Security GO2-99-073, Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.7901999-04-19019 April 1999 Forwards Rev 39 to WNP-2 Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Approved Plan.Encl Withheld IAW 10CFR73.21 & 10CFR2.790 ML17292B6401999-04-13013 April 1999 Requests That WNP-2 Operator Requalification Program Be Granted one-time Extension Beyond Requirement in 10CFR55.59(a)(2) for Annual Operating Tests ML17292B6371999-04-12012 April 1999 Forwards Response to NRC 990211 RAI Re Util Request for Amend to Secondary Containment & SBGTS TS ML17292B6281999-04-0606 April 1999 Informs NRC That Insp Interval Ending Date for ISI Program Plan Has Been Extended by One Year to Dec 12,2005 Due to Changes in Plant Refueling Outage Schedule GO2-99-060, Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1)1999-03-26026 March 1999 Submits Rept of Status of WNP-2 Decommissioning Fund as of 981231,IAW 10CFR50.75(f)(1) ML17292B6131999-03-24024 March 1999 Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Nozzle Safe End. Info Will Be Used to Assist NRC in Review of WNP-2 ISI Activities Associated with Evaluation of Planar Indication ML17292B5991999-03-16016 March 1999 Informs That Listed Property & Liability Insurance Coverage for WNP-2 Is in Force,In Compliance with Licensing Responsibilities Delineated in 10CFR50.54(w)(3) ML17292B5911999-03-16016 March 1999 Forwards 1998 Environ Operating Rept, Per Reporting Requirements of Section 5.4.1 of WNP-2 Epp.No Design or Operational Changes or Tests in 1998 Involved Unreviewed Environ Question ML17292B5941999-03-16016 March 1999 Forwards NRC Form 396, Certification of Medical Exam by Facility Licensee, & NRC Form 398, Personal Qualification Statement - Licensee, for MD Comstock,Mc Naulty & RR Nelson.Without Encls ML17292B6001999-03-16016 March 1999 Responds to Weakness Noted in Insp Rept 50-397/98-24. Corrective Actions:Developed Document to Identify Areas Needing Improvement,Assigned Responsibility for Actions & Provided Milestones for Achievement ML17292B5901999-03-11011 March 1999 Forwards Hard Copy of Addl Occupational Exposure Data Requested in GL 94-04,per 990303 e-mail.Original Electronic Version Was Corrupted ML17292B5681999-03-0101 March 1999 Forwards Radioactive Effluent Release Rept for 1998, IAW 10CFR50.36a(a)(2) & TS 5.6.3 & Complete Copy of WNP-2 ODCM Per TS 5.5.1 ML17292B5651999-02-22022 February 1999 Forwards Relief Request 2ISI-20,proposing Alternate Exam Expected to Reduce Dose Significantly & Still Provide Adequate Safety & Quality.Attached Relief Request Will Be Used to Support ALARA Dose Reduction Efforts During Maint ML17292B5581999-02-0404 February 1999 Requests Change to Co Which Modified WNP-2 OL to Reflect Schedule for Implementing Thermo-Lag 330-1 Fire Barrier C/As.Change Requested to Reflect That Final Implementation of C/As Will Be Completed During Fall 1999 Not Spring 1999 1999-09-09
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CATEGORY j.
Pj . REGULATOO INFORMATION DISTRIBUTION+STEM (RIDE)
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ACCESSIOA NBR:9701060119 DOC.DATE! 96/12/27 NOTARIZED: NO DOCKET g FACI1::50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BEMIS,P.R. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards rept "Qualification of Supply Sys Use of RODEX2 Code," for Gap qonductance cal,culation in topical rept WPPSS-FTS-131, "Applications Topical Rept for BWR Design
& Analysis. Rept provides justification for use of code.
DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR I ENCL 5 SIZE: /
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA PD4-2 'PD COLBURN,T INTERNAL: ACRS 1 E CENTER 01 NRR/DE/ECGB/A 1 NRR NRR/DRCH/HICB 1 NRR/DSSA/SPLB NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT OGC/HDS3 1 EXTERNAL: NOAC 1 1 NRC PDR NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL ,9
P
<<p WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 December 27, 1996 G02-96-252 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control'Desk Washington, D.C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 CODE FOR THE GAP CONDUCTANCE CALCULATION IN TOPICAL REPORT WPPSS-FTS-131, "APPLICATIONS TOPICAL REPORT FOR BWR DESIGN AND ANALYSIS"
References:
- 1) Letter GO2-93-021, dated January 27, 1993, from G. C. Sorensen to NRC, "Nuclear Plant No. 2, Operating License NPF-21, Notification of Request for NRC Review of Topical Report WPPSS-FTS-131, Rev. 1,
'Applications Topical Report for BWR Design and Analysis'"
- 2) Letter dated June 4, 1996, TG Colburn (NRC) to JV Parrish (SS),
"Issuance of Amendment for the Washington Public Power Supply System Nuclear Project No. 2 (TAC No. M95247)"
In response to discussions with the staff, the attached report provides justification for Supply System use of the NRC approved RODEX2 computer code. This code was developed by Siemens Power Corporation (SPC) for calculation of gap conductances in reactor fuel for applications to BWR transient analysis as described in Revision 1 of the "Applications Topical Report for BWR Design and Analysis, WPPSS-FTS-131A" issued to section 6.9.3.2 of the WNP-2 Technical Specifications by Reference 2. No specific action by the staff is requested by this letter.
970i060119 96i227 PDR ADQCK 05000397 P PDR
Page 2 QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 Should you have any questions or desire additional information regarding this matter, please call me or Ms. L. C. Fernandez at (509) 377-4147.
Respectfully, P. R. Bemis Vice President, Nuclear Operations Mail Drop PE23 Attachment CC: JE Dyer - NRC RIV KE Perkins, Jr., - NRC RIV, Walnut Creek Field Office TG Colburn - NRR NS Reynolds - Winston & Strawn DL Williams - BPA / 399 RC Barr - NRC, WNP-2 / 297N
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QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 CODE 0
Attachment Page 1 of 11 P~ur 0 e The purpose of this report is to document the Supply System's qualification to use SPC's RODEX2'ode to calculate gap conductances. This qualification will satisfy the requirement of using RODEX2 for gap conductance calculations in the Supply System reload methodology documented in the report WPPSS-FTS-131A~, as issued by the NRC to section 6.9.3.2 of the WNP-2 Technical Specification.
VeriTic tion nd Validati n n Tn tallation of R DEX2 a u I stem The RODEX2 code developed by SPC and approved by the NRC'as been installed on the Supply System IBM workstation RISC6000. The Supply System performed installation verification and validation of the code according to the Supply System Engineering Directorate Manual EDP 2.16 "Production Computer Program and Data Base Control," which conforms to FSAR Chapter 17 Quality Assurance requirements. Three sample problems provided by SPC4 for the purpose of validating the code installation were run on the Supply System computer.
These sample problems, designated as Cases 1, 2, and 3, had 160, 166, and 365 time steps respectively. The Supply System results were identical to the SPC results for all analytical steps. Attached Tables 1, 2, and 3 provide a comparison of the Supply System and SPC results for the final time step. Only the final step is shown in the tables because the effect of any differences between the analytical results at intermediate time steps would proliferate, thereby affecting the results for the final time step.
It should be noted that the first three rows in Tables 1, 2, and 3 are computer input, and the remaining rows are from the computer output. As can be seen, the Supply System outputs are identical to the SPC outputs. This demonstrates that the RODEX2 code as installed on the Supply System IBM workstation RISC6000 provides identical results as the same code installed on SPC computers.
Methodolo for eneratin ore Avera e and Hot Channel G onductanc The methodology used for the calculation of core average and hot channel gap conductances is the same as that of SPC except the codes used for burnup histories as explained below. The Supply System uses SIMULATE-E, which is part of the physics codes as approved by the NRC for WNP-2 reload analysis'o compute burnup histories for each batch and for the hot bundles.
SPC uses MICROBURN-B.
The main input to RODEX2 includes mechanical design parameters, such as pellet and clad materials and dimensions, and burnup histories, which include LHGR histories, axial power profiles, coolant enthalpy, coolant flow rates and reactor pressure.
The axial and radial fuel rod powers used as input to the RODEX2 code are determined from core follow and predicted control rod step-through SIMULATE-E calculations. These SIMULATE-Ecalculations are used as input to determine both the core average gap conductance and hot channel gap conductance for each fuel design.
,QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 CODE Attachment Page 2 of 11 The core average gap conductance is determined by RODEX2 using as input the SIMULATE-E core follow and predicted control rod step-through calculations as follows. First, the average gap conductance is determined for each batch in the core for the initial conditions of the transient. This is done by using SIMULATE-E to calculate the batch average axial power history, the batch average radial power history and the batch average flow history from the time when the batch was first inserted into WNP-2 until the exposure where the transient is initiated.
These average batch histories are input to RODEX2 to calculate an average gap conductance for each batch.
Following SPC's methodology, the core average gap conductance is then determined from the batch average gap conductances by power and assembly weighing each batch according to the following formulation:
(BAGS xNq xBARPq)
CAGC-(NgxBARPg )
where CAGC = Core Average Gap Conductance, BAGC = Batch Average Gap Conductance, N = Number of Assemblies and BARP = Batch Average Radial Power.
The hot channel gap conductance for each fuel design (8x8, 9x9-9X, etc.) is determined by RODEX2 using as input the SIMULATE-E core follow and predicted control rod step-through calculations as follows. For each fuel design at the point of initial conditions for the transient, the assembly with the minimum critical power ratio is selected as the hot channel. Then for each selected assembly, the axial power history, radial power history and flow history are calculated using SIMULATE-E from the time it is first inserted into the WNP-2 core until the exposure where the transient is initiated. These histories are input to RODEX2 to calculate the hot channel gap conductance for each fuel design. Once the RODEX2 calculation has determined the historical effects on the gap conductance, the gap conductance in the hot channel is determined at varying power conditions. The resulting gap conductances are used in subsequent analysis as described in the Applications Topical Report WPPSS-FTS-131A2. This approach is consistent with SPC's application of RODEX2.
u I stem Res I nd om arison with SPC Tables 4 through 7 provide gap conductance calculations and comparisons with SPC results for Cycles 8, 10 and 11. Table 4 gives the core average results. Tables 5 through 7 give the hot channel results. The data in Table 5 through 7 are also plotted as Figures 1 through 6. The gap conductances for Cycle 9 are not compared because the Supply System did not perform the Cycle 9 calculation. The differences in calculated gap conductances are attributed mainly to differences in burnup histories introduced by the different depletion codes (SIMULATE-Eversus MICROBURN-B) and differences in the core follow and rodded depletions used in these codes.
It should be noted that in the gap conductance calculations, the burnup histories for earlier cycles
i, 1'-
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, QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 CODE Attachment Page 3 of 11 (Cycle 7 and earlier for the Cycle 8 analysis, Cycle 6 and earlier for the Cycle 10 and 11 analyses) were based on Haling depletion. The larger differences seen in the 8x8 hot channel gap conductance for Cycle 8 are primarily attributed to the use of a Haling depletion in SIMULATE-E for Cycle 7. These Haling depletions were part of the Supply System approach for determining gap conductances prior to adopting the SPC methodology. However, rodded step-throughs were used for later cycles to be consistent with SPC methodology.
The hot channel gap conductance comparisons are based on analyzing the assemblies that were selected by SPC using MICROBURN-B. The results show excellent agreement.
The differences in gap conductance are summarized below (note: the positive values are non-conservative for core-wide and conservative for hot channel. The impact of the differences for core-wide is much less than the impact for hot channel.)
Percent Difference in a Conductance CI cycle ~ore-Wide gX9 8 4.9% -3,5% 2.9%
10 0.2% -1.9% 0%
11 1.7% 1.4% 0.5%
- Typically, the LHGR for 8X8 hot channel for the b, CPR calculation is -11 kW/ft, and for 9X9 it is -7 kW/ft. The differences listed in the above table are based on these LHGRs, In summary, the Supply System calculated gap conductances for both core average and hot channel compare very closely with SPC's results. The small differences are mainly caused by the different depletion codes used by the Supply System and SPC to generate inputs to RODEX2. It is further concluded that the impact of the differences in gap conductance on thermal limits are within the overall accuracy of the calculations,
. QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 CODE Attachment Page 4 of 11 TABLE 1 CASE 1 -
OUTPUT SUPPLY SYSTEM VERSUS SIEMENS POWER CORPORATION Supply System* Siemens Power Corp.*
Time Step No. 160 160 Time (hours) 17915.2 17915.2 LHGR (kw/ft) 11.7 11.7 Fill Pres. (psia) 1491. 1491.
Therm. Gap (mil) 0.135 0.135 Gap Coef. (Btu/hr/ft'/F) 7429. 7429.
Tclad (F) 777.352 777.352 T-Max (F) 2663.7 2663.7 T-Avg (F) 1644.9 1644.9 T-Sur (F) 845.0 845.0 Release Frac (%) 5.51 5.51 Burnup (GWD/MTU) 49.687 49.687 Contact Pressure (psi) 6142.7 6142.7
- Results are for axial node 7 of a 13-node rod.
~ QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 CODE Attachment Page 5 of 11 TABLE 2 CASE 2 OUTPUT - SUPPLY SYSTEM VERSUS SIEMENS POWER CORPORATION Supply System* Siemens Power Corp.*
Time Step No. 166 166 Time (hours) 11664.0 11664.0 LHGR (kw/ft) 15,5 15.5 Fill Pres. (psia) 254. 254.
Therm. Gap (mil) 0.373 0.373 Gap Coef. (Btu/hr/ft~/F) 3392. 3392.
Tclad (F) 717.414 717.414 T-Max (F) 3330.5 3330.5 T-Avg (F) 1962.0 1962.0 T-Sur (F) 879.8 879.8 Release Frac (%) 1.74 1.74 Burnup (GWD/MTU) 21.317 21.317 Contact Pressure (psi) 126.5 126.5
- Results are for axial node 10 of a 24-node rod.
. QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 CODE Attachment Page 6 of 11 TABLE 3 CASE 3 OUTPUT - SUPPLY SYSTEM VERSUS SIEMENS POWER CORPORATION Supply System* Siemens Power Corp.*
Time Step No. 365 365 Time (hours) 26719.0 26719.0 LHGR (kw/ft) 17.6 17.6 Fill Pres. (psia) 217. 217.
Therm. Gap (mil) 0.386 0.386 Gap Coef. (Btu/hr/ft'/F) 1758. 1758.
Tclad (F) 730.515 730.515 T-Max (F) 3997.2 3997.2 T-Avg (F) 2355.4 2355.4 T-Sur (F) 1004.3 1004.3 Release Frac (%) 5.95 5.95 Burnup (GWD/MTU) 23.699 23.699 Contact Pressure (psi) 181.9 181.9
- Results are for axial node 13 of a 24-node rod.
. QUALIFICATIONOF SUPPLY SYSTEM USE OF RODEX2 CODE Attachment Page 7 of 11 TABLE 4 COMPARISON OF CORE-WIDE GAP CONDUCTANCES Core-Wide Hg p at Rated Power (in Btu/hr/ft'/F):
Cycle Hg~p Hggp Number Supply System Siemens Power Corp. % Diff, 627.6* 598+ 4.9 10 693.6+* 692++ 0.2 774.5** 761+++ 1.7 Supply System used rodded step-through depletion for Cycle 8, but used Haling depletion in earlier cycles (Supply System Calculation No. NE-02-94-13 "Core Wide Gap Conductance for Cycle 8 Using RODEX2").
Supply System used rodded step-through depletion for batches beginning in Cycle 7, but used Haling depletion in earlier cycles (Supply System Calculation No.
NE-02-95-29, "Revised Gap Conductances for Cycles 10 and 11").
+
From Siemens Power Corporation Report EMF-92-039, Revision 1, "WNP-2 Cycle 8 Plant Transient Analysis," June 1992
++ From Siemens Power Corporation Report EMF-94-095, "WNP-2 Cycle 10 Plant Transient Analysis," June 1994
+++ From Siemens Power Corporation Report EMF-95-006, "WNP-2 Cycle 11 Plant Transient Analysis," March 1995
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~ QUALIFICATIONOF PLY SYSTEM USE OF RODE ODE
~ Attachment Page 8 of 11 Table 5 COMPARISON OF HOT CHANNEL GAP CONDVCTANCES FOR CYCLE 8 Hot Channel Gap Conductance for 8x8 Fuel at EOCS LHGR H~ H~
(kW/ft) Supply System~ Siemens Power Corp.~~ % Diff.
4 7
51 -4, 74 - .5 14 15 1752 From upp y ystem a cu ation No. NE- Hot anne ap on uctance Calculation for Cycle 8 Using RODEX2 Code".
From SPC Letter SPCWP-94-016 "RODEX2 Data", Feb. 14, 1994.
Hot Channel Gap Conductance for 9x9 Fuel at EOC8 LHGR H~
(kw/ft) Supply System* Siemens Power Corp.~~ % Diff.
397 381 4.2 429 413 3.9 463 500 484 3.3 542 525 3.2 589 573 2.8 26 2.9 70 689 2.5 780 7 2 2.4 10 8 7 850 2.0 972 956 1.7 12 1102 1087 1.4 13 1265 1254 0.9 1479 1474 0.3 15 17 3 1770 rom upp y ystem a cu ation o. - - - ot anne ap on uctance Calculation for Cycle 8 Using RODEX2 Code".
From SPC Letter SPCWP-94-016 "RODEX2 Data", Feb.14, 1994.
~ QUALIFICATIONOF PLY SYSTEM USE OF RODE ODE Attachment Page 9 of 11 TABLE 6 COMPARISON OF HOT CHANNEL GAP CONDUCTANCES FOR CYCLE 10 Hot Channel Gap Conductance for SxS Fuel at EOC10 LHGR H~ H~
(kW/ft) Supply System~ Siemens Power Corp.~~ % Diff.
1 7 22 541 55 711 74 1 7 1474 7 1774 17 -1.4 From upp y ystem cu ation No. E- Revis ap on uctance or Cycle 10 and 11" From SPC letter dated September 26, 1995, "RODEX2 Data", SPCWP:042:95 Hot Channel Gap Conductance for 9x9 Fuel at EOC10 LHGR H~ H~
(kW/ft) Supply System~ Siemens Power Corp.~~ % Diff.
382 381 0.2 415 414 0.24 450 0.24 487 487 530 529 0.19 578, 578 634 634 699 699 77 776 10 868 8 8 980 980 12 1119 1120 -0.09 13 1299 1301 -0.15 14 1537 1541 -0.26 15 18 1 1868 -0.37 rom upp y ystem a cu ation o. - - ap on uctance tor yc e 10."
From SPC letter dated September 26, 1995, "RODEX2 Data", SPCWP:042:95
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- QUALIFICATIONOF PLY SYSTEM USE OF RODE ODE
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Attachment Page 10 of 11 TABLE 7 COMPARISON OF HOT CHANNEL GAP CONDUCTANCES FOR CYCLE 11 Hot Channel Gap Conductance for 8x8 Fuel at EOC11 LHGR H~ H~
(kW/ft) Supply System~ Siemens Power Corp.~~ .% Diff.
1 4 141 17 17 1.7 1.4 1.7 17 1.4 1 4 1.4 77 1745 1.4 1 5 177 1.2 rom upp y ystem a cu ation No. NE- 74 ap on uctances or yc e 11."
From SPC letter dated September 26, 1995, "RODEX2 Data", SPCWP:042:95 Hot Channel Gap Conductance for 9x9 Fuel at EOC11 LHGR H~ H~p (kW/ft) Supply System* Siemens Power Corp. ** % Diff.
383 384 -0.26 417 418 -0.24 452 453 -0.22 492 492 536 536 587 586 0.17 0.47 717 712 0.70 793 0.88 10 902 891 1.2 1028 1013 1.5 12 1192 1170 1.9 13 1410 1377 2.4 14 1711 1660 3.1 15 2154 2072 4.0 rom upp y ystem a cu ation o. - - - ap on uctances or yc e 11."
From SPC letter dated September 26, 1995, "RODEX2 Data," SPCWP:042:95
- QUAI IFICATION OF PLY SYSTEM USE OF RODEX2 ODE
" Attachment Page 11 of 11 REFERENCES
- 1. K. R. Merckx et al., "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," XN-NF-81-58(P)(A), Revision 2 and Supplement 1 and 2, March 1984
- 2. Letter, G02-93-021, dated January 27,1993, from G. C. Sorensen to NRC, "Nuclear Plant No. 2, Operating License NPF-21, Notification of Request for NRC Review of Topical Report WPPSS-FTS-131A, Rev. 1, 'Applications Topical Report for BWR Design and Analysis'"
- 3. Letter from C.O. Thomas (NRC) to J.C. Chandler (SPC), "Acceptance for Reference of Licensing Topical Report XN-NF-81-58(P), 'RODEX2 Fuel Rod Thermal Mechanical Response Evaluation Model', Revision 2", Nov. 16, 1983
- 4. Letter SPCWP-93-0009 from Y. V. Fresk, Siemens, to R.A. Vopalensky, Supply System, "RDX2LSE Computer Code," dated January 25, 1993
- 5. Letter from James Clifford, NRC, to G. C. Sorensen, Supply System, "Evaluation of Topical Report WPPSS-FTS-127 'Qualification of Core Physics for BWR Design and Analysis'TAC No. M76783)," dated October 23, 1992
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